IR 05000327/2019010
| ML19115A223 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/25/2019 |
| From: | Jonathan Montgomery NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR 2019010 | |
| Download: ML19115A223 (22) | |
Text
April 25, 2019
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000327/2019010 AND 05000328/2019010
Dear Mr. Shea:
On March 14, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant Units 1 and 2, and discussed the results of this inspection with Mr. Matt Rasmussen and other members of your staff. On April 10, 2019, the NRC inspectors discussed the final results of this inspection with Mr. Jonathan Johnson and other members of your staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
This finding involved a violation of NRC requirements.
If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at Sequoyah.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos.: 05000327 and 05000328 License Nos.: DPR-77 and DPR-79
Enclosure:
Inspection Report 05000327/2019010 and 05000328/2019010
Inspection Report
Docket Number(s):
05000327 and 05000328
License Number(s):
Report Number(s):
05000327/2019010 and 05000328/2019010
Enterprise Identifier:
I-2019-010-0025
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah Nuclear Plant, Units 1 and 2
Location:
Chattanooga, TN 37402
Inspection Dates:
February 25, 2019, to March 14, 2019
Inspectors:
C. Franklin, Reactor Inspector
M. Greenleaf, Reactor Inspector
R. Patterson, Reactor Inspector
E. Stamm, Senior Reactor Inspector
M. Yeminy, NRC Contractor
H. Leake, NRC Contractor
Approved By:
Jonathan M. Montgomery, Acting Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Design Bases Assurance Inspection at Sequoyah Units 1 and 2 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations
Failure to Demonstrate AC Power System Calculations Conform to Design Bases Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green NCV 05000327,05000328/2019010-01 Closed None 71111.21M The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify or check the adequacy of design of the AC power system.
INSPECTION SCOPE
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components with listed applicable attributes, permanent modifications, and operating experience:
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
Unit 2 Pressurizer Power Operated Relief Valves [2-PCV-068-0340A-A, 0334-B]
- Compliance with the Updated Final Safety Analysis Report (UFSAR),
Technical Specifications (TS), and Technical Requirements Manual (TRM)
- Adequacy of design and licensing documents
- Adequacy of operating procedures
- Adequacy of recent modifications
- System health reports accurately reflect system health
- Translation of vendor specifications
- Design verification of control logic for automatic functions
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples)
- (1) Unit 0 Emergency Raw Cooling Water Travelling Water Screens [0-SCN-067-0471, 475, 480, 485]
- Accuracy of design and licensing basis documents
- Material condition and configuration
- Adequacy of the operating procedures
- Adequacy of corrective actions
- Surveillance testing satisfies all essential parameters
- Backwash pump and traveling screen preventive and corrective maintenance is adequate to maintain required availability
- Compliance with vendor instructions for installation, maintenance, and operation of the pumps
- Adequacy of recent modifications
- System Health Reports accurately reflect system health
- Adequacy of internal flood evaluations
- (2) Unit 1 6900V Shutdown Board 1A-A [1-BDA-202-CM-A]
- Compliance with UFSAR, TS, and TS Bases
- Adequacy of maintenance and corrective action activities
- Material condition and configuration
- Design requirements (Voltage, Current, etc.)
- Coordination and relaying
- Design verification of bounding design basis events, including fast bus transfer between offsite power sources
- (3) Unit 2 Charging Pump 2A-A/Room Cooler [2-PMP-062-0108, 2-CLR-030-0183]
- Accuracy of design and licensing basis documents
- Material condition and configuration
- Adequacy of the operating procedures
- Adequacy of corrective actions
- Adequate net positive suction head (NPSH) and available margin
- Sufficient pump head and flow rate to account for all scenarios
- Surveillance testing satisfies all essential parameters
- Pump preventive and corrective maintenance is adequate to maintain required availability
- Room heat load vs cooling capacity to maintain maximum allowable room temperature
- Impact of turbine building environment on room temperature
- Single failure criterion for room cooling
- Compliance with vendor instructions for installation, maintenance, and operation of the pumps
- Adequacy of recent modifications
- Adequate calculations of pump minimum flow and NPSH (for all sources of suction)
- System Health Reports accurately reflect system health
- (4) Unit 1 Refueling Water Storage Tank (RWST) Level Transmitters [1-LT-063-0050-D, -
0051-E, 0052-F, 0053-G]
- Compliance with UFSAR and TS
- Accuracy of design and licensing basis documents
- Adequacy of corrective actions
- Consistency of tank and transmitter design drawings with design bases
- Effectiveness of emergency operating procedures, including time-critical operator actions associated with RWST outlet valve failure to close
- Capability of design, including calculations for instrumentation setpoints and uncertainties, tank capacity, vortexing limits, pump flow rates, and RWST inventory depletion during time-critical actions
- Adequacy of required completion times for automatic and manual switchover from the RWST to the containment sump during safety injection
- (5) Unit 2 Steam Generator Level Control Valves [2-LCV-003-148-B, -156-A]
- Accuracy of design and licensing documents
- Adequacy of operating procedures
- Capability to adequately control flow rate to the steam generators
- Adequacy of corrective actions
- Compliance with vendor instructions
- Adequacy of recent modifications
- System health reports accurately reflect system health
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
- (1) Replacement of 125V DC Vital Battery Charger I [DCN 23209]
- (2) Degraded Non-Conforming MOV Modifications [DCN 23623]
- (3) Replace 8 EDG Starting Air Compressors, Dryers, and Pressure Switches [DCN
===23634]
- (4) Replacement of Shutdown Board PCB 6.9kV/480V Transformers [DCN 23680]
Review of Operating Experience Issues (IP Section 02.06)===
- (1) NRC Information Notice (IN) 2017-06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the Direct Current Distribution System
- (2) NRC IN 1997-60, Incorrect Unreviewed Safety Question Determination Related to Emergency Core Cooling System Swapover from the Injection Mode to the Recirculation Mode
INSPECTION RESULTS
Failure to Demonstrate AC Power System Calculations Conform to Design Bases Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems
Green NCV05000327,05000328/2019010-01 Closed None 71111.21M The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify or check the adequacy of design of the AC power system.
Description:
On October 31, 2012, the NRC issued license amendment numbers 332 and 325 to the licensee, granting a change to their Technical Specifications 3.8.1 and 4.8.1. The change was necessary as a result of modifications to the plant design and operating configuration that would install generator circuit breakers (GCBs) and new unit station service transformers (USSTs) to allow their use as a qualified offsite power supply.
Technical Specification Bases B 3.8.1 stated, "Offsite power will normally be supplied from the USSTs to the 6.9kV Shutdown Boards via the 6.9 kV Unit Boards, and will automatically transfer at least one power supply to an alternate power supply ([Common Station Service Transformer] CSST A or CSST C) on a trip of the Power Circuit Breakers (PCBs)." Also stated in the licensees Bases, the licensee identified the following electrical configurations that demonstrate compliance with their Technical Specification requirement of maintaining two qualified offsite circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System:
1. Two Common station service transformers (CSSTs) windings X and Y providing power
to their respective 6.9 kV unit boards.
2. A train and unit specific USST with the ability to fast transfer to a respective CSST
upon loss of a unit specific USST and a CSST different than that of the one receiving a postulated fast transfer (X and Y windings) providing power to their respective 6.9 kV unit boards.
In all analyzed cases, whenever a USST was being utilized as a qualified offsite source, the ability to fast transfer to a CSST was explicitly required to be available. The transfer is necessary because the opening of the stations PCBs (needed to isolate the generator in the event of a failure of the non-1E GCBs) would remove power to the USSTs, thereby removing their capability of providing offsite power during normal plant operations, as well as design basis accidents, and postulated environmental events.
In reviewing the licensees design of their fast transfer system and its impact on the safety related 6.9 kV shutdown boards, inspectors were referred to the licensees calculation SQNETAPAC, Auxiliary Power System, Rev. 89. The purpose of the calculation was to analyze and document the acceptability of the plant AC power system as defined in UFSAR Sections 8.2 and 8.3. Inspectors reviewed the calculation and determined that the calculation failed to model limiting voltage transients following design basis fast (automatic) transfers from the USSTs to the CSSTs, to verify that they would not result in actuation of the degraded voltage relays - leading to a loss of offsite power.
The licensee provided SQN-APS-005, Fast Bus Transfer, Rev. 2, as their documented analysis of the effect fast transfer would have on their 1E power system. As stated in the licensees response to a request for additional information (dated August 23, 2012), the calculation was intended to present an analysis demonstrating that the transfer would not exceed 1.33 Volts per Hertz, in accordance with American National Standards Institute (ANSI) standard C50.41. Inspectors reviewed the calculation and determined that, while the calculation analyzed a transfer from the CSST to the USSTa transfer that could be less limiting, the calculation failed to analyze a bus transfer from the USST to the CSST. In addition to this, inspectors determined that the calculation failed to comprehensively model the stations configuration including, but not limited to, the licensees failure to:
1. Evaluate the effects non-motor (static) loads would have on the voltage and phase
angle of the bus being transferred during the dead bus time.
2. Consider the tripping of the main generator excitation system prior to tripping the main
generator (approximately 10 cycles), during which time the voltage of the shutdown board could experience greater transient conditions due to the loss of some voltage regulation provided by the excitation system.
3. Consider the motoring of the main generator, and its lagging phase angle effects.
Inspectors concluded that calculations SQNETAPAC and SQN-APS-005 failed to demonstrate the adequacy of the design of the fast transfer scheme necessary to qualify the USSTs as offsite sources, and failed to ensure the integrity of the safety-related equipment powered by the offsite circuits. Additionally, inspectors noted that the station could not provide previous runs of the ETAP software which generated the outputs for calculation SQNETAPAC because the previous runs were not retrievable, and that the base model used in the calculation did not represent the as-designed condition of the stations electrical system.
Corrective Action(s): The licensee determined the equipment to be operable. The licensee plans to revise calculations SQNETAPAC and SQN-APS-005.
Corrective Action Reference(s): CRs 1494559, 1497075, and 1498362
Performance Assessment:
Performance Deficiency: The team determined that the failure to check or verify the adequacy of the design of the AC power system was a performance deficiency of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone. Specifically, the revised outputs of the calculations would result in a significant loss of margin, reducing the reliability of the AC power system.
Significance: The inspectors assessed the significance of the finding using Appendix A, Significance Determination of Reactor Inspection Findings for At - Power Situations. The finding was determined to be Green since it was a deficiency affecting the design or qualification of a mitigating structure, system, or component and its operability was maintained.
Cross-cutting Aspect: Not Present Performance. No cross cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, states, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Contrary to the above, since February 17, 2012, the licensee failed to verify or check the adequacy of design of the AC Power System. Specifically, the licensee failed to demonstrate the adequacy of the design of the fast transfer scheme necessary to qualify the USSTs as offsite sources and ensure the integrity of the safety-related equipment powered by the offsite circuits.
Enforcement Action: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 14, 2019, the inspectors presented the design bases assurance inspection results to Mr. Matt Rasmussen and other members of the licensee staff.
- On April 10, 2019, the inspectors presented the final design bases assurance inspection results to Mr. Jonathan Johnson and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
03D53EPMWLL063094
AFW Hydraulic Analysis
Rev. 16
1-FCV-63-073
Documentation of Design Basis Review, Required
Thrust Calc and Valve & Actuator Capability
Assessment for 1-FCV-63-073
Rev. 6
2-FCV-63-040
Documentation of Design Basis Review, Required
Thrust Calc and Valve & Actuator Capability
Assessment for 2-FCV-63-040
Rev. 5
30-D053-EPM-BVC-
2788
Determination of Required ERCW and Air Flow rates
to ESF Room Coolers
Rev. 9
AFW Hydraulic Analysis
AFW Level Control Valve Opening Time
Rev. 1
B45 870106427
MELB Safe Shutdown Analysis
Rev. 4
B45870106428
MELB Flooding Study
Rev. 18
B87951205003
ERCW Screen Wash System Hydraulic Analysis
Rev. 3
CDQ0000632016000333
Evaluation of Refueling Water Storage Tank for
Beyond Design Basis Tornado and Flood Loads
Rev. 0
EDQ0000632014000103
Instrumentation Evaluation for RWST Volume during
Time Critical Action (TCA) Associated with RWST
Versus Sump Switchover - Level Monitoring, System
Rev. 0
GEN-EEB-MS-TI28-0002 Generic Accuracy Calculation - Eagle 21 I/O
Demonstrated Accuracy Calculation
Rev. 2
MDQ0009992106000323 Damage Assessment & Repair Strategy for Appendix
R Cold Shutdown Motor Operated Valves
Rev. 0
MDQ0072980034
CCP, SIP, and RHR Pump NPSH Evaluation
Rev. 11
MDQ0999-980039
MOV Thrust Requirements Considering Pressure Lock
Using ComEd Methodology
Rev. 5
OSG7-0020
Safety Injection System (063) 10CFR50.49 Category
and Operating Times
Rev. 20
SCG4M01104
Steam Generator AFW Level Control Valves Seismic
Qualification Evaluations
Rev. 0
Calculations
SQN-00-D059 EPM-
RJP-061091
Generic Letter 89-10 MOV Population At Sequoyah
Units 1 & 2
Rev. 19
SQN-30-D53-EPM-
ASD01-031287
HVAC Cooling Load Calculation Auxiliary Building
CCP Rooms Elevation 669
Rev. 3
SQN-63-D053 EPM-
RJP-030191
Documentation of Design Basis Review, Required
Thrust Calc and Valve & Actuator Capability
Assessment for 1-FCV-63-025
Rev. 7
SQN-APPR-1
Analysis of AC/DC Instrument and Control (I&C)
Power Systems to Identify Associated Circuits - 10 CFR 50 Appendix R
Rev. 20
SQN-APS-003
480VAC APS Class 1E Load Coordination Study
Rev. 88
SQN-APS-005
Fast Bus Transfer Analysis
Rev. 2
SQN-CPS-051
Circuit Protection Device Evaluation
Rev. 67
SQN-EEB-MS-TI28-0015 Instrument Accuracy Calc: 1-LT-63-50, -51, -52, -53
Rev. 13
SQN-EEB-PL&S
Precautions, Limitations and Setpoint for NSSS
Rev. 55
SQN-NTB-
NDQ0063980038
RWST and Containment RHR Safety and Operational
Limits, RWST Setpoint Required Accuracy, and
LBLOCA and SBLOCA Sump Minimum Levels
Rev. 17
SQN-NTB-SQS20110
Emergency and Abnormal Procedure Setpoints
Rev. 34
SQN-QN-EEB-MS-TI28-
25
Instrument Accuracy Calc: 1-LT-63-50, -51, -52, -53
Rev. 14
SQN-SQS2-0010
Chemical and Volume Control System Operating
Modes
Rev. 12
SQN-SQS2-169
Maximum Temperature of the Piping on the Discharge
of the Pressurizer SRVs and PORVs Following Valve
Actuation.
Rev. 0
SQNETAPAC
Auxiliary Power System
Rev. 89
TPS-SQN-PLN-EDX000-
000-2002-001
Planning Transmission Study (TSS) - Grid Off-Site
Power, Transient Stability, and Fault Current
Calculation for 2012 and 2016
Rev. 3
Corrective Action
Documents
CR 1133416
CR 1158718
CR 1161344
CR 1170545
CR 1175834
CR 1177144
CR 1180402
CR 1181710
CR 1183483
CR 1184239
CR 1205951
CR 1210311
CR 1215848
CR 1296320
CR 1316043
CR 1328776
CR 1345254
CR 1389095
CR 1406471
CR 1416535
CR 1435427
CR 1472289
CR 1475587
CR 1476134
CR 1476273
CR 1493816
CR 168601
CR 759027
CR 760336
CR 787960
CR 818759
CR 934663
PER 753504
PER 771351
71111.21M Corrective Action
Documents
PER 934663
Corrective Action
Documents
Resulting from
Inspection
CR 1493643
Drawing Needs to be Updated
CR 1493816
SQN-DC-V-12.2 Issues Found
CR 1493833
FSAR Section 3.1.2 not Updated to Reflect USST
Modification
CR 1493963
Identified Plant Light Out in ERCW Room
CR 1493966
Identified Standing Water in 1A-A Bay
CR 1493970
Identified FME in ERCW Room Sump
CR 1493973
Identified Clogged Drains in ERCW Building
CR 1494101
Inadequate Testing of Discharge Check Valves
CR 1494419
Unconservative Heat Load from Surface of Pipes
CR 1494452
Comprehensive Pump Test Lists Quarterly Pump Test
as Alternate
CR 1494461
Quarterly Pump Test is not Credited for Check Valve
Closure
CR 1494559
SQNETAPAC Rebaseline Needed
CR 1494707
Apparent Inadequate 50.59 Evaluation for PIC 23696
CR 1496014
Calculation SQNETAPAC, Revision 90, Documents
Several Instances of Using MVARs for 30 Seconds
After a LOCA to Support Grid Voltage
CR 1496213
NRC-Identified RWST Tornado Vulnerability
CR 1496325
Plant Grid Interface Meeting Minutes Reference Typo
CR 1496841
Incorrect TRM References in Calculation SQN-EEB-
MS-TI28-0025, Rev. 14
CR 1497075
SQNETAPAC Revisions using Base Revision Rather
than As-designed Condition
CR 1497921
Calculation Error in NDQ0063980038
CR 1497928
Calculation Error in EDQ0000632014000103
Enhancement
CR 1498200
FSAR Not Revised to Capture New SBLOCA Limiting
Scenario
71111.21M Corrective Action
Documents
Resulting from
Inspection
CR 1498253
Lack of Critical Thinking When Evaluating the Last 2B-
B CCP Pump Comprehensive Test
CR 1498291
2012 NRC Submittal Validation Information
CR 1498327
CR 1498336
Higher Pump Motor Horse Power Was Not Used in a
Heat Load Calculation
CR 1498356
CCP Comprehensive Pump Test Uses Computer
Points Rather Than M&TE Equipment
CR 1498362
Calculations SQNETAPAC and SQN-APS-005 Not
Bounding with Regard to Fast Bus Transfer Scenario
CR 1498642
NRC Identified (NDQ0063980038 Needs an
Enhancement Revision to Clarify)
CR 1498643
The PM Issued for Replacement of Unit 2 Room
Coolers Was In an Inactive Status and Should Be
Reactivated
CR 1498719
Reynolds Number Outside the Range for Equation
Applicability
CR 1498781
Based on Frequency of Cleaning the CCP Room Unit
Coolers, Reevaluate Whether a Fouling Factor of
0.001 is Adequate
CR 1499162
1E to Non-1E Coordination Issue
Drawings
0-15E500-1
Key Diagram, Station Aux Power System
Rev. 56
0-15E500-3
Transformer Taps & Voltage Limits - Aux Power
System
Rev. 44
1, 2 - 47W610-63-2
Mechanical Control Diagram Safety Injection System
Rev. 34
1, 2 - 47W610-68-6
Mechanical Control Diagram Reactor Coolant System
Rev. 17
1,2-45N657-5
Wiring Diagrams, Separation & Mis Aux RLYS
Schematic Diagrams
Rev. 27
1,2-45N703-1
Wiring Diagrams 125V Vital Battery Board I Single
Line - Sheet 1
Rev. 83
1,2-45N703-2
Wiring Diagrams 125V Vital Battery Board II Single
Line - Sheet 2
Rev. 44
1,2-45N703-3
Wiring Diagrams 125V Vital Battery Board III Single
Line - Sheet 3
Rev. 49
71111.21M Drawings
1,2-45N765-1
Wiring Diagram 6900V Shutdown Aux Power
Schematic Diagram SH-1
Rev. 35
1,2-47W309-3
Mechanical Large Reservoirs
Rev. 0
1-47W600-143
Mechanical Instruments & Controls
Rev. 9
1-47W600-241
Mechanical Instruments & Controls
Rev. 8
1-5655D26-16
Functional Diagrams, Turbine Trips, Runbacks &
Other Signals
Rev. 1
2-47W803-2
Flow Diagram Auxiliary Feedwater
Rev. 78
2-47W809-1
Flow Diagram Chemical and Volume Control System
Rev. 75
Engineering
Changes
D23169
Addition of Leak off Piping and Collection System to
ERCW Pumps
Rev. 0
D23623
Degraded Non-Conforming MOV Modifications -
Gears/Actuators/Motor/Cable Reroute
Rev. A
DCN 23209
Replacement of 125V DC Vital Battery Charger I
Rev. A
DCN 23396A
RWST Swap-over Revised Procedural Actions
Considering Interruption of ECCS Flow
Rev. A
Miscellaneous
B25900219001
Letter Westinghouse to TVA Sequoyah CH/SI Pump
Motor Horsepower
Dated
2/8/90
CNL-16-011
Letter TVA to NRC Technical Specification Change to
Extend the Allowed Completion Time to Restore
Essential Raw Cooling Water System Train to
Operable from 72 Hours to 7 Days
Dated
3/11/16
DCN 23680
Replacement of Shutdown Board PCB 6.9kV/480V
Transformers
Rev. A
IST Evaluation
for 2-LCV-3-156
Completed
6/23/16
IST Evaluation
for 1-LCV-3-148
Completed
10/19/16
IST Evaluation
for 1-LCV-3-156
Completed
7/14/16
Letter from NRC to TVA
Apparent Violation Closure Inspection Report 05000327/2013014 NS 05000328/2013014
Dated
2/11/13
71111.21M Miscellaneous
Memorandum
Memorandum from James
- R. Regg, Chief
Transmissions Systems operations Manager, to
Ronald
- K. Gladney, Communications Requirements
for Sequoyah Nuclear Plant (SQN) Alternate
Alignment
Dated
10/21/02
Memorandum
Memorandum from John M. Campbell to James R.
Regg and
- B. David Till, Sequoyah Nuclear Plant
(SQN) - Off-Site Power Requirements &
Communications Protocols
Dated
3/31/06
NEDP-4
Q-List and UNID Control
Rev. 26
Sequoyah Nuclear Plant Units 1 and 2
Dated
March 1979
OPT200.AC6.9KV
6.9 KV Electrical Distribution System
SCN 17-52
SAR Change Request
Dated
5/17/01
SEG#OPL273S1902
AFW Inside Out
Rev. 0
SO-18-040
2-FCV-67-146 Degraded Stroke Values
Dated
11/30/18
SQN-DC-V-11.2
Design Criteria Document, 125V Vital Battery System
Rev. 12
SQN-DC-V-11.4.1
Design Criteria Document, Normal and Emergency AC
Auxiliary Power Systems
Rev. 24
SQN-DC-V-12.2
Design Criteria Document, Separation of Electric
Equipment and Wiring
Rev. 16
SQN-DC-V-13.9.3
Design Criteria Document, Auxiliary Building
Ventilation and Cooling
Rev. 6
SQN-DC-V-13.9.8
Design Criteria Document, Auxiliary Feedwater
System
Rev. 29
SQN-DC-V-27.2
Design Criteria Document, Chemical and Volume
Control System
Rev. 35
SQN-DC-V-27.3
Design Criteria Document, Safety Injection System
Rev. 24
SQN-DC-V-27.4
Design Criteria Document, Reactor Coolant System
Rev. 24
SQN-DC-V-27.9
Design Criteria Document, Reactor Protection System
Rev. 17
SQN-DC-V-3.0
Design Criteria Document, The Classification of
Piping, Pumps, Valves, and Vessels
Rev. 21
71111.21M Miscellaneous
SQN-DC-V-46.0
Design Criteria Document, Seismic/Structural
Qualification of Seismic Category I and I(L) In-Line
Valves and Other In-Line Fluid System Components
Rev. 3
SQN-VD-A391-0963
Anchor/Darling Valve CO. Carbon Steel Nuclear
Valves
Dated
3/4/12
SQN-VD-A391-2863
Anchor/Darling Valve CO. Maximum Thrust
Calculations
Dated
3/4/12
SQN-VTD-A998-0010
200 AMP Battery Charger Instriction [Sic] Manual
Rev. 1
SQN-VTD-G182-0050
Installation/Maintenance Instructions for ITE Medium
Voltage Power Circuit Breakers 7.5HK
Rev. 3
SQN-VTD-G182-0710
Brown Boveri Instructions for I-T-E Single Phase
Voltage Relays
Rev. 1
SQN-VTD-G182-0720
Brown Boveri Instructions for Single Phase Voltage
Relays ITE-27N Undervoltage Relay ITE-59N
Overvoltage Relay
Rev. 2
SQN-VTD-T020-0030
Project Technical Manual Power Operated Relief
Valves
Rev. 3
SQN-VTD-W120-3810
Instruction Manual for Unit 1 and 2 Centrifugal
Charging Pumps
Rev. 22
SQN-VTM-G182-0030
Gould Inc. (Formally I-T-E Imperial Corporation) Indoor
and Outdoor Metal Clad Switchgear and Components
Rev. 54
SQN-VTM-T020-0010
Target Rock Corp. Solenoid Operated Valves
Rev. 17
SS-E18.10.01
Standard Specification for Environmental Qualification
Requirements for Safety Related Electrical Equipment
Rev. 4
TVA-7493
Westinghouse Letter
Dated
8/15/79
TVA-DT-01
Standard Specification, Dry Type, Power & Distribution
Transformer
Rev. 0
Operability
Evaluations
PDO 1496213
PDO 753504
Procedures
0-AR-M26-A
Annunciator 0-XA-55-26A
Rev. 43
71111.21M Procedures
0-PI-EBM-000-001.2
Battery Bank High Level Equalize Charge (Systems
2, 244, 250)
Rev. 39
0-SO-250-1
25 Volt DC Vital Power System
Rev. 76
0-TI-OPS-000-004.0
Time Critical Operator Actions
Rev. 9
1-AR-M1-C
AC/DC Control Power 1-XA-55-1C
Rev. 59
2-SI-ICC-068-455.0
2-SI-ICC-068-455.0 COPS PCV-68-340A CC
Rev. 18
2-SI-IFT-068-456.0
2-SI-IFT-068-456.0 COPS PCV-68-334 FT
Rev. 18
2-SI-SXP-062-201.B
Centrifugal Charging Pump 2B-B Performance Test
Completed
1/31/19
2-SI-SXP-062-203.0
Centrifugal Charging Pumps 2A-A and 2B-B
Comprehensive pump Test and Check Valve Test
Completed
11/28/18
2-SI-SXV-003-232.1
Turbine Driven Auxiliary Feedwater Pump Check
Valve Test Unit 2
Rev. 4
Rev. 4
External Flooding
Rev. 59
Degraded Grid or Abnormal Voltage Conditions
Rev. 15
DS-M18.2.21
Motor Operated Valve Thrust and Torque Calculations
Rev. 24
DS-M18.2.22
MOV Design Basis and JOG Review Methodologies
Rev. 8
E-0
Reactor Trip or Safety Injection
Rev. 40
ES 1.3
Transfer to RHR Containment Sump
Rev. 22
ES 1.3
Transfer to RHR Containment Sump
Rev. 21
Transfer to RHR Containment Sump
Rev. 23
GOI-6
General Operating Instructions, Apparatus Operations
Rev. 184
NEDP-2
Design Calculation Process Control
Rev. 23
NEDP-8.0
Evaluations for Procurement of Materials, Items, and
Services
Rev. 5
NPG-SPP-01.16
Condition Report Initiation
Rev. 2
NPG-SPP-06.9.3
Post-Modification Testing
Rev. 10
NPG-SPP-09.14
Generic Letter 89-13 Implementation
Rev. 4
NPG-SPP-09.26.14
Motor Operated Valve Program
Rev. 4
NPG-SPP-09.3
Plant Modifications and Engineering Change Control
Rev. 30
NPG-SPP-09.4
CFR 50.59 Evaluations of Changes, Tests, and
Experiments
Rev. 12
NPG-SPP-22.300
Corrective Action Program
Rev. 12
71111.21M Procedures
NPG-SPP-22.500
Operating Experience Program
Rev. 7
NPG-SSP-09.1.20
Inservice Testing Program Requirements
Rev. 1
NPG-TREND
NPG Trending Manual
Rev. 9
OPDP-8
Operability Determination Process and Limiting
Conditions for Operation Tracking
Rev. 24
TI-28
Technical Instruction, Curve Book
Rev. 334
Work Orders
111842240
114412576
114605899
115320081
115420993
115420998
116532954
116859442
117064518
117107091
117352923
117353016
117673650
117732985
117908899
117908901
118021552
118266140
118318157
118594134
118799855
118817993
119127713
119145564
119198833
119199046
119201492
119266171
71111.21M Work Orders
119421920
119793040
119819464
119819466